Basic Info
Fission Yield
element
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Information about Silver-120:
 |  |  | | | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 2.02167E-05 |
4.07618E-05 |
| U-235 with 1.0 MeV
| 6.26905E-05 |
1.36953E-04 |
| U-238 with 1.0 MeV
| 5.32610E-05 |
2.44592E-04 |
| Pu-239 with 0.0253 eV
| 4.32012E-05 |
7.40957E-05 |
| Pu-239 with 1.0 MeV
| 7.26798E-05 |
1.31726E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 2.86923E-05 |
2.86923E-05 |
| U-235 with 1.0 MeV
| 1.04834E-04 |
1.04834E-04 |
| U-238 with 1.0 MeV
| 8.90659E-05 |
8.90659E-05 |
| Pu-239 with 0.0253 eV
| 6.13127E-05 |
6.13127E-05 |
| Pu-239 with 1.0 MeV
| 1.21539E-04 |
1.21539E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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